ML20198E809

Proposed Tech Specs Pages Re Change to TS Safety Limit 2.1.1.2,changing Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13

ML20198E809
Person / Time
Site:	River Bend
Issue date:	12/16/1998
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20138M271	List: ML20198E809 RBG-44721, Application for Amend to License NPF-47,proposing Change to TS Safety Limit 2.1.1.2.Amend Will Change Two Recirculation Loop MCPR Limit from 1.13 to 1.12 & Single Recirculation Loop MCPR Limit from 1.14 to 1.13.Proprietary Encl Withheld
References
NUDOCS 9812240149
Download: ML20198E809 (2)

Text

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. SLs 2.0 2.0 5AFETY LIMITS-(SLs)-

2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 104 rated core flow:

THERMAL POWER shall be s 25% RTP.

2.1.1.2 'With.the reactor steam dome pressure 2 785 psig and core flow a 10% rated core flow:

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• MCPR shall be z '1.43 for two recirculation loop I operation or 2 (A4 for single recirculation loop

• operation. /,/3 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel. '

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.

2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the corporate executive responsible for overall plant nuclear safety.

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• Values applicable to Cycle operation only.

RIVER BEND 2.0-1 Amendment No, M % 99 9812240149 981216 '

PDR ADOCK 05000458 p PDR I. , _ _ .- ._ - ._. __ .

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\ Reporting Requirements f4 5.6 h*'

5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version);*

2) NEDC-32489P (April 1996), "T-Factor Setdown Elimination Analysis for River Bend Station" (for power and flow dependent limits methodology only as evaluated and approved by Safety Evaluation and License Amendment 100 dated October 10,1997).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS)_ limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

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• For Cycle JP, specific documents were approved in the Safety Evaluation dated

-/ October 5, 19974 to support License Amendment No./99(

RIVER BEND 5.0-19 Amendment No. 84 96 99 100 j

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